ND-21-0228, ITAAC Closure Notification on Completion of ITAAC 2.3.08.02.i (Index Number 415)

ITAAC Closure Notification on Completion of ITAAC 2.3.08.02.i (Index Number 415)

ML21063A498
Person / Time
Site:	Vogtle
Issue date:	03/04/2021
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-21-0228
Download: ML21063A498 (8)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tei Docket No.: 52-025 MAR 0 A 2021 ND-21-0228 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.08.02.1 flndex Number 4151 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtie Electric Generating Plant(VEGP)

Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.08.02.1 [Index Number 415], for verifying the SWS Pump Flow Through CCS Heat Exchanger and that controls

/ displays are available in the Main Control Room (MCR) as listed in Table 2.3.8-1. The closure process for this ITAAC is based on the guidance described in NEI 08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52", which is endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Kelli Roberts at 706-848-6991.

Respectfully submitted, Michael J. Yoxi:

Regulatory Affairs Dir ctor Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 ITAAC Completion of ITAAC 2.3.08.02.1 [Index Number 415]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-21-0228 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)

Mr. D. L. McKlnney (w/o enclosures)

Mr. M. D. Meier (w/o enclosures)

Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. R. L. Belike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv Commission Ms. M. Bailey (w/o enclosures)

Mr. M. King Ms. A. Veil M C. P. Patel M . G. J. Khouri M C. J. Even M B. J. Kemker Ms. N. C. Coovert M C. Welch M . J. Gaslevic M . O. Lopez-Santiago M . G. Armstrong M M. Webb M . T. Fredette M . C. Santos M B. Davis M J. Vasquez M . J. Eargle M E. Davidson M . T. Fanelli M S. Rose Ms. K. McCurry

U.S. Nuclear Regulatory Commission ND-21-0228 Page 3 of 3 Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinohouse Electric Company. LLC Dr. L. OrianI (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NU8, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GD8 Associates, Inc.

Mr. 8. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-0228 Enclosure Page 1 of 5 Southern Nuclear Operating Company ND-21-0228 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 Completion of ITAAC 2.3.08.02.1 [Index Number 415]

U.S. Nuclear Regulatory Commission ND-21-0228 Enclosure Page 2 of 5 ITAAC Statement Desian Commitment

2. The SWS provides the nonsafety-related function of transferring heat from the component cooling water system to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling.

3. Controls exist in the MCR to cause the components identified in Table 2.3.8-1 to perform the listed function.

4. Displays of the parameters identified in Table 2.3.8-1 can be retrieved in the MCR.

Inspections/Tests/Analvses i) Testing will be performed to confirm that the SWS can provide cooling water to the CCS heat exchangers.

Testing will be performed on the components in Table 2.3.8-1 using controls in the MCR.

Inspection will be performed for retrievability of parameters in the MCR.

Acceptance Criteria i) Each SWS pump can provide at least 10,000 gpm (gallons per minute) of cooling water through its CCS heat exchanger.

Controls in the MCR operate to cause the components listed in Table 2.3.8-1 to perform the listed functions.

The displays identified in Table 2.3.8-1 can be retrieved in the MCR.

ITAAC Determination Basis This ITAAC requires testing and inspections be performed to demonstrate that the Service Water System (SWS) provides the nonsafety-related function of transferring heat from the Component Cooling Water System (CCS)to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling, ensure controls in the Main Control Room (MCR)operate to cause the components listed in Table 2.3.8-1 to perform the listed function, and ensure the displays of parameters identified in Table 2.3.8-1 can be retrieved in the MCR.

n Each SWS pump can provide at least 10.000 gpm of cooling water through its CCS heat exchanaer.

Multiple ITAAC were performed to demonstrate the SWS provided the nonsafety-related function of transferring heat from the component cooling water system to the surrounding atmosphere to support plant shutdown and spent fuel pool cooling. Testing was performed in accordance with Unit 3 preoperational test procedure 3-SWS-ITPP-501 (Reference 1), utilizing

U.S. Nuclear Regulatory Commission ND-21-0228 Enclosure Page 3 of 5 Work Order 1051753(Reference 2), to verify that each SWS pump provided at least 10,000 gpm of cooling water through its COS heat exchanger.

Initial conditions were established with the SWS train B pump in service with a temporary flow instrument installed upstream of the COS B heat exchanger. The temporary flow instrument was monitored and the flow value was determined in accordance with B-GEN-ITPA-004(Reference

6) and verified to be greater than 10,000 gpm. This differs from the Uncompleted ITAAC Notification but is in compliance with plant procedures for non-safety systems. This testing was repeated with the SWS pump A and the A COS heat exchanger.

The test results demonstrated that the Unit 3 B SWS pump provided 11,088 gpm through Unit 3 B COS heat exchanger and the Unit 3 A SWS pump provided 11,187 gpm through Unit 3 A COS heat exchanger and was documented in References 1 and 3.

These test results confirmed that each SWS pump provided at least 10,000 gpm of cooling water through its COS heat exchanger.

Controls in the MCR operate to cause the components listed in Table 2.3.8-1 to perform the listed functions.

Testing was performed in accordance with Unit 3 component test work order SNC922111 (Reference 4)to verify that controls exist in the MCR and the controls operate to cause the components listed in COL Appendix C Table 2.3.8-1 (Attachment A)to perform the listed functions.

The component tests were conducted using controls at an operator work station in the MCR with the A SWS pump in service. SWS cooling tower fan A was started using its temperature controller from the operator work station. The B SWS pump was then started, its discharge valve was verified to open, and the A SWS pump was removed from service. The SWS cooling tower cells were then aligned to place the B cooling tower cell and the B cooling tower fan in service. SWS cooling tower fan B was started using its temperature controller from the operator work station. The SWS pumps were then realigned to place A SWS pump in service and the A SWS pump discharge valve was verified to open.

These test results confirmed that controls in the MCR operate to cause the components listed in Attachment A to perform the listed functions and was documented in References 4 and 5.

The displavs identified in Table 2.3.8-1 can be retrieved in the MCR.

An inspection was performed in accordance with component test work order SNC922111 (Reference 4)to verify that the displays Identified in COL Appendix C Table 2.3.8-1 (Attachment B)can be retrieved in the MCR.

An inspection was conducted at an operator work station in the MCR and verified all the displays Identified in Attachment B can be retrieved. This confirmed that the displays identified in Attachment B can be retrieved in the MCR and was documented in References 4 and 5.

The completed test results (References 1 through 5)confirm that each SWS pump can provide at least 10,000 gpm of cooling water through its CCS heat exchanger, that the controls in the

U.S. Nuclear Regulatory Commission ND-21-0228 Enclosure Page 4 of 5 MGR operate to cause the components listed In Table 2.3.8-1 to perform the listed functions, and that the displays identified in Table 2.3.8-1 can be retrieved in the MGR.

References 1 through 6 are available for NRG inspection as well as Unit 3ITAAG Completion Package (Reference 7).

ITAAC Finding Review In accordance with plant procedures for ITAAG completion, Southern Nuclear Operating Company(SNG) performed a review of all findings pertaining to the subject ITAAG and associated corrective actions. This review found there were no relevant ITAAG findings associated with this ITAAG. The ITAAG completion review is documented in the ITAAG Completion Package for ITAAG 2.3.08.02.1 (Reference 6)and is available for NRG review.

ITAAC Completion Statement Based on the above information, SNG hereby notifies the NRG that ITAAG 2.3.08.02.1 was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

Systems, structures, and components verified as part of this ITAAG are being maintained in their as-designed, ITAAG compliant condition in accordance with approved plant programs and procedures.

References (available for NRC Inspection)

1. 3-SWS-ITPP-501, Rev. 3.0, "Service Water System Preoperational Test"

2. Work Order 1051753,"(ITAAG) 3-SWS-ITPP-501 Preoperational Test"

3. SV3-SWS-ITR-800415, Rev. 0,"Unit 3 Recorded Results of Service Water System Flow:

ITAAG 2.3.08.02.1, Item 2.1"

4. Work Order SNG922111,"PERFORM ITAAG 2.3.08.02.1 Items 3 and 4"

5. SV3-SWS-ITR-801415, Rev. 0,"Unit 3 Recorded Results of Service Water System Component Test: ITAAG 2.3.08.02.1, Items 3 and 4"

6. B-GEN-ITPA-004, Rev. 22.0,"Conduct of Test"

7. 2.3.08.02.i-U3-GP-Rev0, ITAAG Completion Package

U.S. Nuclear Regulatory Commission ND-21-0228 Enclosure Page 5 of 5 Attachment A "Excerpt from COL Appendix C Table 2.3.8-1 Equipment Name" Tag No." Control Function" Service Water Pump A (Motor) SWS-MP-01A Start Service Water Pump B (Motor) SWS-MP-01B Start Service Water Cooling Tower Fan A (Motor) SWS-MA-01A Start Service Water Cooling Tower Fan B (Motor) SWS-MA-01B Start Service Water Pump A Discharge Valve SWS-PL-V002A Open Service Water Pump B Discharge Valve SWS-PL-V002B Open Attachment B "Excerpt from COL Appendix C Table 2.3.8-1 Equipment Name" Tag No." Display" Service Water Pump A (Motor) SWS-MP-01A Yes(Run Status)

Service Water Pump B (Motor) SWS-MP-01B Yes(Run Status)

Service Water Cooling Tower Fan A (Motor) SWS-MA-01A Yes(Run Status)

Service Water Cooling Tower Fan B (Motor) SWS-MA-01B Yes(Run Status)

Service Water Pump 1A Flow Sensor SWS-004A Yes Service Water Pump 1B Flow Sensor SWS-004B Yes Service Water Pump A Discharge Valve SWS-PL-V002A Yes(Valve Position)

Service Water Pump B Discharge Valve SWS-PL-V002B Yes (Valve Position)

Service Water Pump A Discharge SWS-005A Yes Temperature Sensor Service Water Pump B Discharge SWS-005B Yes Temperature Sensor Service Water Cooling Tower Basin Level SWS-009 Yes